An interesting oxidation phenomenon of Cr coatings on Zry-4 substrates in high temperature steam environment-Reference-Cited by-同舟云学术

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An interesting oxidation phenomenon of Cr coatings on Zry-4 substrates in high temperature steam environment

Published:2019-08 Issue: Volume:156 Page:117-124
ISSN:0010-938X
Container-title:Corrosion Science
language:en
Short-container-title:Corrosion Science

Author:

Han Xiaochun,Xue Jiaxiang,Peng Shuming,Zhang Haibin

Funder

the China National Science and Technology Major Special Project “Research on Accident Tolerant Fuels Key Technologies”

National Natural Science Foundation of China

Science and Technology Development Foundation of China Academy of Engineering Physics

Publisher

Elsevier BV

Subject

General Materials Science,General Chemical Engineering,General Chemistry

Reference20 articles.

1. Accident tolerant fuels for LWRs: a perspective;Zinkle;J. Nucl. Mater.,2014

2. Material selection for accident tolerant fuel cladding;Pint;Metall. Mater. Trans. E,2015

3. Protective coatings on zirconium-based alloys as accident-tolerant fuel (ATF) claddings;Tang;Corros. Rev.,2017

4. Performance of iron–chromium–aluminum alloy surface coatings on Zircaloy 2 under high-temperature steam and normal BWR operating conditions;Zhong;J. Nucl. Mater.,2016

5. Protection of zirconium by alumina- and chromia-forming iron alloys under high-temperature steam exposure;Terrani;J. Nucl. Mater.,2013

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1. Comparative study on high-temperature air and steam oxidation of Cr-coated Zr-4 alloy through experimental and DFT calculation;Journal of Nuclear Materials;2025-01

2. The hydrogen-helium-vacancy interaction and hydrogen-vacancy clusters formation mechanisms in chromium: A first-principles study;Journal of Nuclear Materials;2024-12

3. Performance evaluation of accident tolerant Cr-coated Zr alloy cladding under accident conditions based on a refined degradation model;Progress in Nuclear Energy;2024-11

4. Microstructural characteristics of multilayers and interfaces of Cr-coated Zircaloy-4 cladding based on elemental diffusion under high-temperature steam oxidation;Journal of Nuclear Materials;2024-10

5. Early-stage diffusion and oxidation behavior of Cr-Nb coated Zr alloy accident tolerant fuel cladding materials at 1200°C–1500°C;Journal of Nuclear Materials;2024-10

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